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Title: Container assessment: corrosion study of HLW container materials. Quarterly progress report, July-September 1981. Volume 1, No. 3

Technical Report ·
DOI:https://doi.org/10.2172/5348464· OSTI ID:5348464

Work has been started on the corrosion and hydrogen embrittlement behavior of commercially pure titanium (ASTM Grade 2), TiCode-12 (ASTM Grade 12), and OFHC copper, which are primary candidate materials for high level waste containers. The test environment used is a simulated brine solution typical of bedded salt at 150 C or room temperature. The immersion test results for these materials are in reasonable agreement with previous screening test results of Sandia National Laboratory; electron beam welded titanium and TiCode-12 samples show higher corrosion rates than the non-welded samples. To understand the difference between titanium and TiCode-12 in uniform and crevice corrosion, electrochemical tests were performed. While the initial repassivation behavior is similar in terms of charge density transfer after scratching tests in 1 M HCl solution at 80 C, titanium shows an active peak in polarization curves in brine at room temperature while TiCode-12 does not. Also, the open circuit corrosion potential of TiCode-12 is about 300 mV more anodic than that of titanium in 0.1 M HCl plus 0.9 M KCl solution at 85 C. Slow strain rate embrittlement and impact embrittlement have been observed in cathodically hydrogen charged commercially pure titanium and TiCode-12 in tension and buckling tests. C-ring and U-bend specimens of titanium and TiCode-12 have been designed and a slow strain rate test machine is being built to study stress corrosion cracking. Alternating Current Impedance and Scanning Reference Electrode Techniques are ready for pitting studies. For the study of radiation-induced corrosion, an irradiation cell was set up in the gamma pool to estimate quantitatively the oxidants as well as hydrogen produced by the gamma radiation in the brine solutions. 35 refs., 18 figs., 5 tabs.

Research Organization:
Brookhaven National Lab., Upton, NY (USA). Nuclear Waste Management Div.
DOE Contract Number:
AC02-76CH00016
OSTI ID:
5348464
Report Number(s):
NUREG/CR-2317-Vol.1-No.3; BNL-NUREG-51449-Vol.1-No.3; ON: TI86000121
Country of Publication:
United States
Language:
English